US2949415A - Electrical measuring means for nuclear reactors - Google Patents

Electrical measuring means for nuclear reactors Download PDF

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US2949415A
US2949415A US630608A US63060856A US2949415A US 2949415 A US2949415 A US 2949415A US 630608 A US630608 A US 630608A US 63060856 A US63060856 A US 63060856A US 2949415 A US2949415 A US 2949415A
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fuel element
electrical
fuel
channel
contact devices
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US630608A
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Stubbs John Jeffrey
Watts Dennis Michael
Ingham Terence
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English Electric Co Ltd
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English Electric Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K7/00—Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat ; Power supply therefor, e.g. using thermoelectric elements
    • G01K7/02—Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat ; Power supply therefor, e.g. using thermoelectric elements using thermoelectric elements, e.g. thermocouples
    • G01K7/023—Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat ; Power supply therefor, e.g. using thermoelectric elements using thermoelectric elements, e.g. thermocouples provided with specially adapted connectors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/102—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain the sensitive element being part of a fuel element or a fuel assembly
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • FIG.2 ELECTRICAL MEASURING MEANS FOR NUCLEAR REACTORS Filed Dec. 26, 1956 2 Sheets-Sheet 2 FIG.2
  • This invention relates to nuclear reactors of the kind having fuel elements disposed in fuel element channels formed in the moderator structure, and to electrical measuring means for such reactors.
  • a nuclear reactor includes, in combination, a moderator structure having formed therein a plurality of fuel element channels, a plurality of fuel elements disposed in the respective fuel element channels, at least one of the fuel elements having mounted thereon an electrical measuring device for measthing a desired parameter of the fuel element, two electrical contact devices, and electrical leads connecting the electrical measuring device with the respective contact devices, and for each fuel element carrying an electrical measuring device two electrical contact devices secured in the fuel element channel containing the fuel element and positioned so as to make electrical contact with the respective contact devices on the fuel element, and two electrical conductors secured in the moderator structure, being connected at one end to the respective electrical contact devices fixed in the channel and passing at the other end out of the reactor so as to enable the electrical measuring device to be connected in circuit when desired with electrical measuring apparatus disposed outside the reactor.
  • the electrical contact devices mounted on a fuel element are spaced axially apart on the fuel element, and the two electrical contact devices secured in a fuel element channel for co-operation with the contact devices on a fuel element comprise two arc-shaped contact members disposed concentrically with the fuel element and spaced axially apart in the fuel element channel.
  • each electrical contact device mounted on a fuel element comprises a set of electrical contact members angularly spaced around the fuel element in similar axial positions, and each arc-shaped contact member extends circumferentially only part-way round the fuel element channel, being of a circumferential length such that at least one contact member of the co-operating set makes contact therewith regardless of the angular position of the fuel element in the channel.
  • each fuel element has a plurality of radially-extending spacing members which position the fuel element centrally within a fuel element channel and the electrical contact members mounted on the fuel element are carried on the spacing members.
  • the electrical conductors connected with the arc-shaped electrical contact members are embedded in the moderating material constituting the moderator structure and are not exposed in the fuel element channel.
  • Figure 1 of the drawings shows a sectional elevation of a part of the graphite pile (constituting the said moderator structure) through which passes a fuel element channel, the section being such as to illustrate clearly the arrangement of the fuel elements disposed in the fuel channel.
  • Figure 2 of the drawings shows a View looking in the direction of arrow A of Figure 1.
  • Fig. 1 shows three finned fuel elements 10 disposed vertically on end one above the other in the vertical fuel element channel 11.
  • the latter has a circular cross section of diameter greatly exceeding the diameter of the fuel element fins so that a cooling medium may be passed along the channel whereby to cool the fuel elements.
  • Each fuel element is positioned transversely in the fuel element channel by means of two axially-spaced sets of spacing members 10a and 10b which radiate from the upper end of each fuel element, the lower end of each fuel element being positioned transversely by means of a cone 100 formed thereon which rests in a conical cup 10d formed in the upper end of the next lower fuel element.
  • Each set of spacing members 100 and 10b comprises three outwardly projecting members which are spaced at equal angles around the fuel element in similar axial positions, the spacing members constituting the upper set being axially in line with the spacing members constituting the lower set.
  • Spring-loaded contacts 13 are mounted at the ends of the spacing members and are arranged to press radially outwards on to the wall 14 bounding the fuel element channel, two of the contacts in so doing pressing against two arc-shaped electrical contact strips 15 and 16 disposed permanently in the wall of the fuel element channel.
  • the spring-loaded contacts are electrically insulated in known manner from the spacing members on which they are mounted, by means not shown, but are electrically connected to the leads of a thermo-couple 17 embedded in the lower part of the fuel element, the contacts on the upper set of spacing members 10a being connected in parallel by leads 18 to one of the thermo-couple leads, and the contacts on the lower set of spacing members 1% being connected in parallel by leads 19 to the other thermo-couple lead.
  • the thermo-couple leads are located in slots 20 formed in the cooling fins 21 of the fuel element and are maintained in position in the slots by spring clips 22.
  • the arc-shaped contact strips 15 and 16 are disposed concentrically with the fuel elements in axially-spaced positions opposite the two sets of spacing members 10a and 10b, and are arranged to extend over arcs of the channel wall sub-tending angles slightly greater than so that whatever the angular position of the fuel element relative to the fuel element channel at least one of the contacts mounted on the upper set of spacing members 10a is in contact with the contact strip 15 and at least one of the contacts mounted on the lower set of spacing members 10b is in contact with the contact strip 16.
  • the contact strips 15 and 16 comprise arc-shaped strips of wire gauze disposed in a recess 23 formed in the wall 14 bounding the channel, the contact surface of the gauze being flush with the surface of the wall, and the gauze being set in an insulating material 2A comprising fused magnesia whereby to electrically insulate it from the graphite blocks forming the pile .12.
  • the contact strips 15 and 16 are electrically connected to external thermo-couple terminals (not shown) situated outside the reactor by means of electrical conductors 25 and 26 built into the graphite blocks forming the pile during the process of building the pile.
  • the thermo-couples 17 mounted on the fuel elements may be connected, when desired, in circuit with electrical temperature measuring or indicating apparatus disposed outside the reactor by connecting such apparatus with the external thermo-couple terminals.
  • the axial spacing of the upper and lower spacing members 10a and 10b and the depth and spacing of the contact strips and 116 are arranged so as to allow for differential thermal expansion between the columns of fuel elements and the reactor pile when in operation.
  • thermo-couple leads since the fuel elements have no trailing thermo-couple leads the removal and insertion of the fuel elements is rendered a less diflicult task than heretofore. Furthermore, since the thermo-couples mounted on the fuel elements will be connected to external terminals whatever the angular position of fuel elements relative to the fuel element channel, there is no necessity to align the fuel elements in any particular angular position when inserting them in the pile.
  • thermo-couples disposed outside the reactor by means similar to those described above for connecting the thermo-couples with external terminals.
  • a nuclear reactor including, in combination, a moderator structure having formed therein a plurality of fuel element channels and a plurality of fuel elements disposed in the respective fuel element channels, the provision of at least one fuel element having mounted thereon an electrical measuring device for measuring a desired parameter of the fuel element, two electrical contact devices, and electrical leads connecting the electrical measuring device with the respective contact devices, and for each fuel element carrying an electrical measuring device two electrical contact devices secured in the fuel element channel containing the fuel element and positioned so as to make electrical contact with the respective contact devices on the fuel element, and two electrical conductors secured in the moderator structure, being connected at one end to the respective electrical contact devices fixed in the channel and passing at the other end out of the reactor so as to enable the electrical measuring device to be connected in circuit when desired with electrical measuring apparatus disposed outside the reactor.
  • the electrical contact devices mounted on a fuel element are spaced axially apart on the fuel element, and the two electrical contact devices secured in a fuel element channel for co-operation with the contact devices on a fuel element comprise two arc-shaped contact members disposed concentrically with the fuel element and spaced axially apart in the fuel element channel.
  • each electrical contact device mounted on a fuel element comprises a set of electrical contact members angularly spaced around the fuel element in similar axial positions, and wherein each arch-shaped contact member extends circumferentially only part-way round the fuel element channel, being of a circumferential length such that at least one contact member of the co-operating set makes contact therewith regardless of the angular position of the fuel element in the channel.
  • each fuel element has a plurality of radially-extending spacing members which position the fuel element centrally within a fuel element channel and wherein the electrical contact members mounted on the fuel element are carried on the spacing members.
  • each arc-shaped electrical contact member mounted in a fuel element channel comprises a strip of wire gauze mounted with its contact surface flush with the wall of the fuel element channel and being supported by an electrically insulating material embedded in the fuel element channel wall.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Physics & Mathematics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

"Aug. 16, 1960 J. J. STUBBS ET AL 2,949,415
ELECTRICAL MEASURING MEANS FOR NUCLEAR REACTORS Filed Dec. 26, 1956 2 Sheets-Sheet 1 1950 J. J. STUBBS ETAL 2,949,415
ELECTRICAL MEASURING MEANS FOR NUCLEAR REACTORS Filed Dec. 26, 1956 2 Sheets-Sheet 2 FIG.2
Tia/Mud:
Patented Aug. 16, 1960 ELECTRICAL MEASURING MEANS FOR NUCLEAR nEA'c'roRs John Jeffrey Stubbs, Dennis Michael Watts, and Terence Ingham, all of Whetstone, near Leicester, England, assignors to The English Electric Company Limited, London, England, a British company Filed Dec. 26, 1956, Ser. No. 630,608
Claims priority, application Great Britain Dec. 29, 1955 7 Claims. (Cl. 204-1932) This invention relates to nuclear reactors of the kind having fuel elements disposed in fuel element channels formed in the moderator structure, and to electrical measuring means for such reactors.
According to the present invention a nuclear reactor includes, in combination, a moderator structure having formed therein a plurality of fuel element channels, a plurality of fuel elements disposed in the respective fuel element channels, at least one of the fuel elements having mounted thereon an electrical measuring device for measthing a desired parameter of the fuel element, two electrical contact devices, and electrical leads connecting the electrical measuring device with the respective contact devices, and for each fuel element carrying an electrical measuring device two electrical contact devices secured in the fuel element channel containing the fuel element and positioned so as to make electrical contact with the respective contact devices on the fuel element, and two electrical conductors secured in the moderator structure, being connected at one end to the respective electrical contact devices fixed in the channel and passing at the other end out of the reactor so as to enable the electrical measuring device to be connected in circuit when desired with electrical measuring apparatus disposed outside the reactor.
According to another feature of the invention the electrical contact devices mounted on a fuel element are spaced axially apart on the fuel element, and the two electrical contact devices secured in a fuel element channel for co-operation with the contact devices on a fuel element comprise two arc-shaped contact members disposed concentrically with the fuel element and spaced axially apart in the fuel element channel.
According to a further feature of the invention each electrical contact device mounted on a fuel element comprises a set of electrical contact members angularly spaced around the fuel element in similar axial positions, and each arc-shaped contact member extends circumferentially only part-way round the fuel element channel, being of a circumferential length such that at least one contact member of the co-operating set makes contact therewith regardless of the angular position of the fuel element in the channel.
According to yet another feature of the invention each fuel element has a plurality of radially-extending spacing members which position the fuel element centrally within a fuel element channel and the electrical contact members mounted on the fuel element are carried on the spacing members.
Preferably the electrical conductors connected with the arc-shaped electrical contact members are embedded in the moderating material constituting the moderator structure and are not exposed in the fuel element channel.
Other features of the invention will appear from the following description, with reference to the accompanying drawings of a graphite-moderated nuclear reactor according to the invention, the fuel elements of this reactor being arranged in vertical fuel element channels formed in the moderator structure. I
Figure 1 of the drawings shows a sectional elevation of a part of the graphite pile (constituting the said moderator structure) through which passes a fuel element channel, the section being such as to illustrate clearly the arrangement of the fuel elements disposed in the fuel channel.
Figure 2 of the drawings shows a View looking in the direction of arrow A of Figure 1.
Referring now to the drawings, Fig. 1 shows three finned fuel elements 10 disposed vertically on end one above the other in the vertical fuel element channel 11. The latter has a circular cross section of diameter greatly exceeding the diameter of the fuel element fins so that a cooling medium may be passed along the channel whereby to cool the fuel elements.
Each fuel element is positioned transversely in the fuel element channel by means of two axially-spaced sets of spacing members 10a and 10b which radiate from the upper end of each fuel element, the lower end of each fuel element being positioned transversely by means of a cone 100 formed thereon which rests in a conical cup 10d formed in the upper end of the next lower fuel element.
Each set of spacing members 100 and 10b comprises three outwardly projecting members which are spaced at equal angles around the fuel element in similar axial positions, the spacing members constituting the upper set being axially in line with the spacing members constituting the lower set. Spring-loaded contacts 13 are mounted at the ends of the spacing members and are arranged to press radially outwards on to the wall 14 bounding the fuel element channel, two of the contacts in so doing pressing against two arc-shaped electrical contact strips 15 and 16 disposed permanently in the wall of the fuel element channel. The spring-loaded contacts are electrically insulated in known manner from the spacing members on which they are mounted, by means not shown, but are electrically connected to the leads of a thermo-couple 17 embedded in the lower part of the fuel element, the contacts on the upper set of spacing members 10a being connected in parallel by leads 18 to one of the thermo-couple leads, and the contacts on the lower set of spacing members 1% being connected in parallel by leads 19 to the other thermo-couple lead. The thermo-couple leads are located in slots 20 formed in the cooling fins 21 of the fuel element and are maintained in position in the slots by spring clips 22.
The arc- shaped contact strips 15 and 16, two per fuel element, are disposed concentrically with the fuel elements in axially-spaced positions opposite the two sets of spacing members 10a and 10b, and are arranged to extend over arcs of the channel wall sub-tending angles slightly greater than so that whatever the angular position of the fuel element relative to the fuel element channel at least one of the contacts mounted on the upper set of spacing members 10a is in contact with the contact strip 15 and at least one of the contacts mounted on the lower set of spacing members 10b is in contact with the contact strip 16. The contact strips 15 and 16 comprise arc-shaped strips of wire gauze disposed in a recess 23 formed in the wall 14 bounding the channel, the contact surface of the gauze being flush with the surface of the wall, and the gauze being set in an insulating material 2A comprising fused magnesia whereby to electrically insulate it from the graphite blocks forming the pile .12. The contact strips 15 and 16 are electrically connected to external thermo-couple terminals (not shown) situated outside the reactor by means of electrical conductors 25 and 26 built into the graphite blocks forming the pile during the process of building the pile. Hence the thermo-couples 17 mounted on the fuel elements may be connected, when desired, in circuit with electrical temperature measuring or indicating apparatus disposed outside the reactor by connecting such apparatus with the external thermo-couple terminals.
The axial spacing of the upper and lower spacing members 10a and 10b and the depth and spacing of the contact strips and 116 are arranged so as to allow for differential thermal expansion between the columns of fuel elements and the reactor pile when in operation.
With the arrangement described, the space between the fuel elements and the channel wall through which the cooling medium flows is devoid of thermo-couple leads, and since the fuel elements have no trailing thermo-couple leads the removal and insertion of the fuel elements is rendered a less diflicult task than heretofore. Furthermore, since the thermo-couples mounted on the fuel elements will be connected to external terminals whatever the angular position of fuel elements relative to the fuel element channel, there is no necessity to align the fuel elements in any particular angular position when inserting them in the pile.
In the case of a liquid-moderated nuclear reactor of the kind in which the fuel elements are disposed within tubes immersed in the liquid moderator the electrical contacts mounted on the fuel elements make electrical contact with electrical contacts such as 15 and 16 mounted in a manner similar to the described in the walls of the tubes and electrically connected to external thermo-couple terminals by means of conductors embedded in the walls of the tubes.
Other electrical devices mounted on the fuel elements and arranged for measuring other physical quantities electrically may be connected with external terminals.
disposed outside the reactor by means similar to those described above for connecting the thermo-couples with external terminals.
What we claim as our invention and desire to secure by Letters Patent is:
1. In a nuclear reactor including, in combination, a moderator structure having formed therein a plurality of fuel element channels and a plurality of fuel elements disposed in the respective fuel element channels, the provision of at least one fuel element having mounted thereon an electrical measuring device for measuring a desired parameter of the fuel element, two electrical contact devices, and electrical leads connecting the electrical measuring device with the respective contact devices, and for each fuel element carrying an electrical measuring device two electrical contact devices secured in the fuel element channel containing the fuel element and positioned so as to make electrical contact with the respective contact devices on the fuel element, and two electrical conductors secured in the moderator structure, being connected at one end to the respective electrical contact devices fixed in the channel and passing at the other end out of the reactor so as to enable the electrical measuring device to be connected in circuit when desired with electrical measuring apparatus disposed outside the reactor.
2. In a nuclear reactor according to claim 1, wherein the electrical contact devices mounted on a fuel element are spaced axially apart on the fuel element, and the two electrical contact devices secured in a fuel element channel for co-operation with the contact devices on a fuel element comprise two arc-shaped contact members disposed concentrically with the fuel element and spaced axially apart in the fuel element channel.
3. In a nuclear reactor according to claim 2, wherein each electrical contact device mounted on a fuel element comprises a set of electrical contact members angularly spaced around the fuel element in similar axial positions, and wherein each arch-shaped contact member extends circumferentially only part-way round the fuel element channel, being of a circumferential length such that at least one contact member of the co-operating set makes contact therewith regardless of the angular position of the fuel element in the channel.
4. In a nuclear reactor according to claim 3, wherein the electrical contact members mounted on a fuel element exert radial pressure on the arc-shaped contact members in the fuel element channel.
5. In a nuclear reactor according to claim 3, wherein each fuel element has a plurality of radially-extending spacing members which position the fuel element centrally within a fuel element channel and wherein the electrical contact members mounted on the fuel element are carried on the spacing members.
6. In a nuclear reactor according to claim 3, wherein each arc-shaped electrical contact member mounted in a fuel element channel comprises a strip of wire gauze mounted with its contact surface flush with the wall of the fuel element channel and being supported by an electrically insulating material embedded in the fuel element channel wall.
7. In a nuclear reactor according to claim 3, wherein the electrical conductors connected with arc-shaped electrical contact members are embedded in the moderating material constituting the moderator structure and are not exposed in the fuel element channel.
References Cited in the file of this patent FOREIGN PATENTS Great Britain Sept. 14, 1942 OTHER REFERENCES 1956. United Nations, N.Y. 1956, pp. 284, 311, 460.)

Claims (1)

1. IN A NUCLEAR REACTOR INCLUDING, IN COMBINATION, A MODERATOR STRUCTURE HAVING FORMED THEREIN A PLURALITY OF FUEL ELEMENT CHANNELS AND A PLURALITY OF FUEL ELMENTS DISPOSED IN THE RESPECTIVE FUEL ELEMENT CHANNELS, TEH PROVISION OF AT LEAST ONE FUEL EEMENT HAVING MOUNTED THEREON AN ELECTRICAL MEASURING DEVICE FOR MEASURING A DESIRED PARAMETER OF THE FUEL ELEMENT, TWO ELECTRICAL CONTACT DEVICES, AND ELECTRICAL LEADS CONNECTING THE ELETRICAL MEASURING DEVICE WITH THE RESPECTIVE CONTACT DEVICES, AND FOR EACH FUEL ELEMENT CARRYING AN ELECTRICAL MEASURING DEVICE TWO ELECTRICAL CONTACT DEVICES SECURED IN THE FUEL ELEMENT CHANNEL CONTAINING THE FUEL ELEMENT AND POSITIONED SO AS TO MAKE ELECTRICAL CONTACT WITH THE RESPECTIVE CONTACT DEVICES ON THE FUEL ELEMENT, AND TWO ELECTRICAL CONDUCTORS SECURED IN THE MODERATOR STRUCTURE, BEING CONNECTED AT ONE END TO THE RESPECTIVE ELECTRICAL CONTACT DEVICES FIXED IN THE CHANNEL AND PASSING AT THE OTHER END OUT OF THE REACTOR SO AS TO ENABLE THE ELECTRICAL MEASURING DEVICE TO BE CONNECTED IN CIRCUIT WHEN DESIRED WITH ELECTRICAL MEASURING APPARATUS DISPOSED OUTSIDE THE REACTOR.
US630608A 1955-12-29 1956-12-26 Electrical measuring means for nuclear reactors Expired - Lifetime US2949415A (en)

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Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3087886A (en) * 1959-02-20 1963-04-30 Thompson Nuclear Energy Co Ltd Temperature measurement apparatus for a nuclear reactor fuel element
US3105037A (en) * 1961-12-04 1963-09-24 Sterling J Weems Concentric tube fuel element spring alignment spacer device
US3110657A (en) * 1959-03-13 1963-11-12 Cie Ind Des Telephones Device for measuring the temperature inside a nuclear reactor
US3111474A (en) * 1956-08-30 1963-11-19 Babcock & Wilcox Ltd Nuclear fuel units
US3132517A (en) * 1959-12-17 1964-05-12 Electricite De France Apparatus for the measurement of temperatures by thermo-couple contacts
US3147193A (en) * 1960-03-02 1964-09-01 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3147194A (en) * 1958-11-04 1964-09-01 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3150056A (en) * 1960-10-10 1964-09-22 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3189525A (en) * 1960-04-19 1965-06-15 Atomic Energy Authority Uk Nuclear reactor fuel elements

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE581296A (en) * 1958-08-01
GB869645A (en) * 1958-10-24 1961-06-07 Atomic Energy Authority Uk Improvements in or relating to fuel elements
DE1202911B (en) * 1960-08-19 1965-10-14 Babcock & Wilcox Ltd Device for receiving and holding the thermocouple supply lines for a nuclear reactor
IT699927A (en) * 1962-06-23
DE3101306C2 (en) * 1981-01-16 1983-01-13 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Method and device for the detection of sodium leaks in steam generators

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB547840A (en) * 1941-10-21 1942-09-14 Brayshaw Furnaces & Tools Ltd Improvements in pyrometers

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB547840A (en) * 1941-10-21 1942-09-14 Brayshaw Furnaces & Tools Ltd Improvements in pyrometers

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3111474A (en) * 1956-08-30 1963-11-19 Babcock & Wilcox Ltd Nuclear fuel units
US3147194A (en) * 1958-11-04 1964-09-01 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3087886A (en) * 1959-02-20 1963-04-30 Thompson Nuclear Energy Co Ltd Temperature measurement apparatus for a nuclear reactor fuel element
US3110657A (en) * 1959-03-13 1963-11-12 Cie Ind Des Telephones Device for measuring the temperature inside a nuclear reactor
US3132517A (en) * 1959-12-17 1964-05-12 Electricite De France Apparatus for the measurement of temperatures by thermo-couple contacts
US3147193A (en) * 1960-03-02 1964-09-01 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3189525A (en) * 1960-04-19 1965-06-15 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3150056A (en) * 1960-10-10 1964-09-22 Atomic Energy Authority Uk Nuclear reactor fuel elements
US3105037A (en) * 1961-12-04 1963-09-24 Sterling J Weems Concentric tube fuel element spring alignment spacer device

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